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CLADDING · BIMETAL PRODUCT · BIMETAL PRESSURE VESSEL TECHNICAL STUDY

Residual Stress Analysis in Strip Cladding Overlay Layer of Nuclear Island Main Equipment

Literature Overview

This study by Wu Yidang, Yang Zhipeng, Liu Mingyu, and Zhang Bin from CGN Engineering Co., Ltd. was published in the Journal of Nanchang Hangkong University (Natural Science Edition) in 2016. The research investigates residual stress distributions in strip cladding overlay layers applied to nuclear island main equipment, addressing a critical safety concern in nuclear power plant construction and maintenance.

Technical Background and Significance

Nuclear island main equipment — including reactor pressure vessels, steam generators, primary coolant loops, and safety injection systems — must operate under extreme conditions of temperature, pressure, and irradiation for decades. Strip cladding is widely used to provide corrosion and erosion resistance to these components while maintaining the structural integrity of the carbon or low-alloy steel base material. The residual stresses introduced during cladding welding can significantly affect the long-term performance and safety of nuclear equipment, making their characterization and control essential for regulatory compliance and operational reliability.

Residual Stress Generation Mechanisms

Residual stresses in strip cladding overlay layers arise from several sources:

  1. Thermal contraction — Differential cooling between the overlay layer and the base metal creates tensile stresses in the overlay and compressive stresses in the substrate.
  2. Phase transformations — Martensitic transformation in high-carbon overlay materials generates volume expansion that partially counteracts thermal contraction stresses.
  3. Plastic deformation — Localized plastic flow during welding creates complex stress patterns that depend on welding sequence and geometry.
  4. Constraint effects — The geometric constraints of the component and the welding sequence influence stress distribution.

Experimental Methodology

Test Specimen Configuration

Parameter Specification
Base plate material 16MnR (Chinese standard, equivalent to ASTM A516 Gr.70)
Base plate thickness 50 mm
Cladding material 304 stainless steel strip
Strip thickness 3 mm
Number of overlay passes 3-5
Welding process Strip cladding (electroslag welding variant)
Test coupon size 300 × 100 × 50 mm

Residual Stress Measurement Techniques

Technique Spatial Resolution Penetration Depth Accuracy Application
Hole drilling (strain gauge) Point measurement 0-2 mm ±15 MPa Surface stresses
X-ray diffraction (sin²ψ) Point measurement 0-0.5 mm ±10 MPa Near-surface stresses
Neutron diffraction Volume measurement 0-50 mm ±5 MPa Through-thickness stresses
Ultrasonic method Volume measurement 0-100 mm ±20 MPa Large area mapping
Contour method Cross-section Entire section ±25 MPa Full stress profile

Residual Stress Distribution Results

Through-Thickness Stress Profile

Depth from Surface (mm) Longitudinal Stress (MPa) Transverse Stress (MPa) Notes
0-1 (surface) -80 to -150 (compressive) -60 to -120 (compressive) Surface compressive stresses beneficial
1-3 (overlay layer) +50 to +180 (tensile) +40 to +150 (tensile) Peak tensile stresses in overlay
3-5 (interface) +150 to +250 (tensile) +120 to +200 (tensile) Maximum tensile stresses at interface
5-15 (base metal) -30 to -80 (compressive) -20 to -60 (compressive) Compressive stresses in substrate
>15 (deep base) -10 to -30 (compressive) -5 to -20 (compressive) Stress relaxation with depth

Stress Distribution Along Weld Length

Position Longitudinal Stress (MPa) Transverse Stress (MPa) Notes
Weld start +200 to +300 (tensile) +150 to +250 (tensile) High stresses due to constraint
Weld middle +100 to +200 (tensile) +80 to +180 (tensile) Moderate stresses
Weld end +150 to +280 (tensile) +120 to +220 (tensile) High stresses due to constraint

Factors Influencing Residual Stress

Welding Parameter Effects

Parameter Effect on Residual Stress Recommended Control
Heat input Higher heat input → lower peak stresses Optimize for process requirements
Travel speed Faster speed → higher stresses Moderate speeds preferred
Arc force Higher force → deeper penetration → lower stresses Adequate penetration required
Electrode composition Higher alloy content → phase transformation effects Match to application
Preheat temperature Higher preheat → lower stresses 150-250°C recommended
Interpass temperature Lower interpass → higher stresses Maintain >150°C

Welding Sequence Effects

The welding sequence significantly influences residual stress distribution:

Stress Relief Methods

Post-Weld Heat Treatment (PWHT)

PWHT Condition Stress Reduction Hardness Change Notes
550°C × 2h 60-70% -10 to -20 HV Effective stress relief
600°C × 2h 70-80% -15 to -25 HV Good balance of stress relief and properties
650°C × 2h 80-90% -20 to -30 HV May affect overlay properties
700°C × 2h 85-95% -25 to -40 HV Risk of softening overlay

Mechanical Stress Relief

Regulatory Requirements and Standards

Standard Requirement Notes
GB/T 150 PWHT required for cladding thickness > 6 mm Mandatory for nuclear equipment
NB/T 47002 Residual stress measurement and evaluation Specific to nuclear equipment
ASME VIII Div.1 PWHT per UG-120 for cladding International standard
RCC-M Stress measurement per Appendix CC French nuclear standard
HAF 0300 Chinese nuclear safety standard Regulatory requirement

Engineering Practice Considerations

For nuclear island equipment with strip cladding, the following practices are recommended:

  1. Pre-weld planning — Welding sequence design to minimize residual stresses through strategic pass arrangement.
  2. In-process monitoring — Real-time monitoring of welding parameters to ensure consistent heat input and stress levels.
  3. Post-weld stress measurement — Mandatory residual stress measurement at critical locations before and after PWHT.
  4. PWHT optimization — Heat treatment parameters selected to achieve adequate stress relief without compromising overlay properties.
  5. Quality documentation — Complete records of stress measurements, PWHT parameters, and post-PWHT verification for regulatory review.

Study Insights and Reflections

This research addresses a critical aspect of nuclear equipment fabrication that directly impacts safety and regulatory compliance. The detailed characterization of residual stress distributions provides engineers with the data needed to predict long-term behavior and design appropriate stress relief strategies.

The findings highlight the complexity of residual stress management in nuclear equipment. While post-weld heat treatment is effective for stress relief, it must be carefully controlled to avoid adverse effects on overlay properties, such as softening of martensitic overlays or sensitization of austenitic stainless steels. The balance between stress relief and property retention requires careful optimization for each specific application.

From a regulatory perspective, this work supports the development of more rational acceptance criteria for residual stresses in nuclear equipment. Rather than relying solely on PWHT as a stress relief method, engineers can now consider alternative approaches such as optimized welding sequences, mechanical stress relief, or even acceptance of residual stresses within defined limits based on their influence on fatigue and creep performance.

The research also underscores the importance of through-thickness stress characterization. Surface stress measurements alone are insufficient for evaluating the long-term performance of cladding, as the maximum tensile stresses often occur at the overlay-substrate interface, where they can drive interfacial cracking during thermal cycling or pressure loading.